Burnup calculation for the PWR spent fuels by JENDL-3

Burnup calculations for PWR spent fuels were made by the SRAC-FPGS system with the different data libraries based on JENDL-2, -3 or ENDF/B-V. The estimated amounts of uranium and plutonium isotopes with these libraries agreed well with one another, and also with the experiment. By comparing the results obtained by JENDL-2 with those by JENDL-3, the large differences were found in the concentrations of U-232 and Np-237. To predict accurately the buildup of U-232, reliable evaluation for minor cross sections such as capture of Pu-236 is needed. The JENDL-3 library improved the prediction accuracy as compared with that by the JENDL-2 library. For the calculation of Np-237 amount, (n,2n) cross section of U-238 becomes important. The calculated amounts of Am-243 and Cm-244 with ENDF/B-V library differed from those with JENDL-2 or JENDL-3. In this case, Pu-242 capture cross section of ENDF/B-V is different from others. (author)